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Characterization of Precipitates in a Niobium-Zirconium-Carbon Alloy

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Characterization of Precipitates in a Niobium-Zirconium-Carbon Alloy DOElNASAll6310-6 NASA TM-I 00848 Characterization of Precipitates in a Niobium-Zirconium-Carbon Alloy INASA-Tn- 100848) PRECIPITATES IN A NIOEIUff-2 IBCONIUR-CARBON ALLOY Final Report tHA3ACTEBIZATIOB(NASA) 18 p OF 888-22981 CSCL 11F Unclas G3/26 0142685 T.L. Grobstein and R.H. Titran National Aeronautics and Space Administration Lewis Research Center Work per.formed for U.S. DEPARTMENT OF ENERGY Nuclear Energy Reactor Systems Development and Technology Prepared for The Metallurgical Society Fall Meeting sponsored by the American Institute of Mechanical Engineers Orlando, Florida, October 5-9, 1986 DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof. Printed in the United States of America Available from National Technical Information Service U.S. Department of Commerce 5285 Port Royal Road Springfield, VA 22161 NTlS price codes1 Printed copy: A02 Microfiche copy: A01 1Codes are used for pricing all publications. The code is determined by the number of pages in the publication. Information pertaining to the pricing codes can be found in the current issues of the following publications, which are generally available in most libraries: €nergy Research Abstracts (ERA); Government Reports Announcements and Index (GRA and I); Scientific and Technical Abstract Reports (STAR); and publication, NTIS-PR-360 available from NTlS at the above address. DOE/NASA/I 631 0-6 NASA TM-100848 Characterization of Precipitates in a Niobium-Zirconium-Carbon Alloy T.L. Grobstein and R.H. Titran National Aeronautics and Space Administration Lewis Research Center Cleveland, Ohio 441 35 Work performed for U.S. DEPARTMENT OF ENERGY Nuclear Energy Reactor Systems Development and Technology Washington, D.C. 20545 Under Interagency Agreement DE-A103-86SF16310 Prepared for The Metallurgical Society Fall Meeting sponsored by the American Institute of Mechanical Engineers Orlando, Florida, October 5-9, 1986 CHARACTERIZATION OF PRECIPATES IN A Nb-Zr-C ALLOY T.L. Grobstein and R.H. Titran National Aeronautics and Space Administration Lewis Research Center Cleveland, Ohio 44135 SUMMARY A niobium alloy with 1 percent zirconium and 0.063 percent carbon by weight was investigated in the as-rolled and annealed conditions, and after high-temperature (1350 and 1400 K) exposure with and without an applied stress. In the as-rolled and in the annealed conditions, large metastable carbides were observed in addition to a regular distribution of small particles. During the high-temperature exposure, the majority of the large carbides were dissolved and a more stable carbide phase formed. This finely dispersed phase had a com- ? position determined to be -70 percent ZrC and -30 percent NbC and showed some d 0 evidence of an orientation relationship with the matrix. The precipitates d I appeared to coarsen slightly after -5000 hr exposure at temperatures between w 1350 and 1400 K. This same high-temperature exposure in the presence of an applied stress resulted in a decrease in the size and in the interparticle spacing of the stable precipitates. However, the composition of the DreciDi- tate phase and its ability to pin dislocations were not affected by the temper- ature or stress conditions INTRODUCTION Niobium-zirconium-carbon alloys were first developed for space energy conversion applications due to their elevated temperature creep res stance , resistance to corrosion by liquid alkali metals, and relatively low density. These alloys rely on complex carbide precipitates for strengthening rather than zirconium oxide precipitation as in binary niobium-1 percent zircon um. It has been established that carbide precipitates are more effective stren theners, but the actual composition, morphology, and aging characteristics o, the second phase in alloys containing carbon have not been fully investigated. Several workers have analyzed precipitation in the Nb-Zr-C system (Arzamozov and Vasil'eva, 1978; Begley et al., 1963; Cuff, 1962; Kissil et al., 1976, 1978; Korotayev et al., 1980, 1981; Lyutyi et al., 1978; Maksimovich et al., 1978; Ostermann and Bollenrath, 1966, Ostermann, 1971; Tsvikilevich, 1980>, but bet- ter understanding of the kinetics of aging reactions with respect to the intended service conditions is required for determination of design parameters. The present work was undertaken to investigate the carbide morphology in a Nb-Zr-C alloy heat treated with and without the presence of an applied stress. The strength of Nb-Zr-C alloys has been shown to be much higher than binary Nb-Zr or Nb-C alloys (DelGrosso et al., 1967; Grigorovich and Sheftel, 1982). It is assumed that the suppression of the transition of the carbide phase from coherent to incoherent (as in binary Nb-C alloys) is due to the for- mation of complexes of carbon, niobium, and zirconium atoms (Korotayev et al., 1981). The increased strength of the ternary alloy is due, therefore, to the precipitation of stable, zirconium-enriched (Nb,Zr>C instead of NbC, which breaks down at lower temperatures than the complex carbide. The increased sta- bility of the (Nb,Zr)C carbide can be attributed to the relative immobility of zirconium in niobium due to its larger atomic size. In addition, although the precipitate phase may contain oxygen, it must be primarily a carbide due to the increased strengthening of Nb-Zr-C alloys over Nb-1Zr with Zr02 precipitates. MAT E R IA L The material used in this study was received from the Oak Ridge National Laboratory in the form of as-rolled, 1-mm thick tensile specimens. This mate- rial was from a single arc-melt followed by a single primary breakdown extru- sion in the 1350 K regime. It was subsequently processed into tube material, which was split and rolled to produce sheet specimens. All material was annealed for 1 hr at 1755 K then 2 hr at 1475 K prior to any testing. Anneal- ing treatments were conducted in titanium sublimation pumped systems at a pres- sure below 10-5 Pa and included wrapping each specimen in cleaned tantalum foi 1. Two of the sheet samples were cut into smaller pieces, wrapped in Nb-1Zr foil, and aged at 1350 K with no applied stress. The heat treatments were carried out in LN2 trapped oil diffusion pumped systems at a pressure of -1 xlO-4 Pa. Several samples were aged in the presence of an appl ied stress at 1350 and 1400 K as described by Titran (1986) in internally loaded chambers at constant load. The vacuum, maintained by bakeable titanium sublimation pumps, was initially -10-5 and ranged to 5x10-7 Pa after several hundred hours. EXPERIMENTAL PROCEDURE Traditional etching for optical and scanning electron metallography was a difficult technique for examining the carbide structure due to the tendency of the particles to fall out of the structure during etching. This was due to the fact that the etchant removed material underneath the particles without attack- ing the carbides. An anodic staining technique was tried (Crouse, 1965), but was not easily interpretable due to the small size of the precipitates. Limited success was obtained using a nitriclhydrofluoric acid etchant. Phase extraction was performed on specimens supported with platinum wires in 100 ml of bromine in 900 ml of methanol with 10 g of tartaric acid in solu- tion. The cell was periodically subjected to ultrasound to disperse any pas- sive layer on the surface of the samples. X-ray analysis was used to identify and to determine the composition of the precipitate phase. Chemical analysis was also performed on the extracted material by inductively coupled plasma atomic emission spectrometry. Transmission electron microscopy foils were cut by electric discharge machining. After the oxide layer was removed by hand polishing, some samples 0 were jet thinned in an electrolyte consisting of 936 ml methanol, 62.8 ml H2SO4, 40 ml butyl alcohol, and 1.5 ml HF. The foils were prepared using a Struers Tenupol apparatus operated at a current density of -27 mA/mm2. Although the large carbide particles tended to fall out of the foils during thinning, adequate thin areas were obtained. In addition, some foils were dimpled then ion-milled. 2 RESULTS AND DISCUSSION Chemical Analysis The oxygen contents increased after aging with and without an applied stress as evidenced in table I, which lists the compositions in both weight percent and atomic percent. This increase was expected and realistic since the vacuum levels at which the material was tested approximated what the material would see during use in space power systems. The oxygen content of the alloy was 2.5 times greater after aging without applied stress, and was four times greater after aging with an applied stress of 40 MPa. These two cases were for approximately the same time and temperature, and the vacuum was one to two orders of magnitude better for the sample under stress. The larger increase in this case is attributed to the increased oxygen mobility in the presence of the applied stress. The increased oxygen content, however, was not discernible through metallography or phase extraction, indicating that most of the oxygen remained in solution.
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